Speaker
Description
The need for accurate knowledge of neutron data in materials as Pb and Bi has increased recently due to the Accelerator Driven System (ADS) and new generation of fast reactor designs with lead or lead-bismuth coolant. The Belgian Nuclear Research Centre (SCK CEN) develops the Multi-purpose hYbrid Research Reactor for High-tech Applications (MYRRHA) that will have a fast sub-critical core cooled with a liquid lead-bismuth eutectic and coupled with an accelerator. Lead integral measurements with fast neutrons are scarce, the only available benchmarks in the IRPhEP database (International Handbook of Evaluated Reactor Physics Benchmark Experiments) come from the BFS critical facility in Obninsk, Russia. To support the design and licensing of MYRRHA, a unique, versatile zero-power reactor VENUS-F was assembled at SCK CEN to serve for validating nuclear data and simulation codes. A large amount of experimental data has been produced during experiments with solid lead as reflector and coolant simulator that need to be analyzed. The objective of this work is to compare various lead data evaluations with existing experimental data from BFS and VENUS-F. For that a geometry model of the OECD benchmark MIX-MET-FAST-006 (BFS-61 cores) and of the VENUS-F reactor (CC7 FREYA core) was created in the Serpent-2 Monte Carlo code. The following integral experiments (published in BFS1-LMFR-EXP-002) in the BFS cores and in the VENUS-F cores were calculated using JEFF, JENDL, ENDF and BROND nuclear data for lead: keff, βeff, spectral indices, radial and axial traverses, and coolant void reactivity effect. The C/E results for BFS and VENUS-F are presented and discussed.